ML20128H336

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Affidavit of Hd Hukill Stating Readiness of TMI-1 to Startup & Complete Low Power Physics & Power Ascension Testing for 100% Power Operation & Opposing Delay in Authorization to Restart.Schedule Encl
ML20128H336
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/23/1985
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To:
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ML20128H326 List:
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SP, NUDOCS 8505300496
Download: ML20128H336 (19)
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UNITED STATES OF AMERICA NUCLEAR REGULA'IORY COMMISSICN BENFE 'IHE 00BEISSICN In the Matter of-

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USNRC Mt:;1xTrOLITAN EDISON COMPANY

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Docket No. 50-289 SP

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15 MAY 24 P4:54

('IhreeLMile. Island Nuclear

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i AFFIDAVIT OF HENRY D. HUKIIL, JR.-

COMOMEAL'IH OF PENNSYLVANIA

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OccNrY OF DAUPHIN

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.The undersigned, Henry D. Hukill, Jr., being duly sworn, deposes

.and says:

1.

I am enployed by GPU Nuclear Corporation as Vice President and Director of Three Mile Island,. Unit No.1 ("TMI-1"). I came to work for the GPU System in June of 1980 and assumed my present position as Vice President and Director of Unit No. -1 in'Septaber 1980. In my capacity as Vice President and Director, I am responsible to the President, GPU Nuclear Corporation, for safe, reliable, and efficient operation of

'IMI-1.

2.

I received a B.S. frcm the United States Naval Academy in 1953..I served on active duty in the Unitec States Navy for more than 22 years. My naval assignments were primarily involved with the

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-m-construction, maintenance, and operation of nuclear subterines and included 5 years in ommand of a nuclear powered missile suhtarine and alnost 4 years as a Senior Naval Officer Assistant to the Director Division of Naval Reactors, Admiral Rickover.

Following retirement frcxn the'U.S. Navy, in December 1975, I served as the Project Operations Manager, Clinch River Breeder Faactor Plant Project for Burns and Roe, Inc., and' then worked for about 3 years as a Senior Civilian Special Assistant for engineering duty officer matters to the Ccmnander, Naval Sea Systems Comnand.

3.

The purpose of my affidavit is to state the readiness of TMI-l to startup and cmplete the low power physics and power ascension testing necessary to bring the plant up to full 100% power operation.

I also want to demonstrate that any delay in the authority to restart will result in an equivalent, day-for-day delay in achievement of full power operation.

4.

Over the past six years since the TMI-2 accident, numerous changes and enhancements have been inplemented in the GPU Nuclear organization and in the management philosophy for operating 'IFI-l in a safe and reliable manner. Additionally, a large number of nodifications have been made to the plant's systems and equignent. Because of the long

- period the plant has been shutdown, and the many changes made in personnel, training, procedures, and equipment, an extensive and conprehensive startup. test program has been developed. This program far exceeds the normal refueling startup test program, botti in depth and duration. The s

primary purposes of this extended restart test program are to validate the effectiveness of-plant nodifications, to thoroughly check out equipment U

-which has been shutdown for a considerable period, and to provide additional time to train operators and allow them to gain increased experience and ocmpetence in plant operations. This restart program has been carefully reviewed with, and approved by, the NPC Staff, which will monitor the quality of our operations and performance during the test program.

5.

To the best of my knowledge, TMI-l is ready frcxn a material l

and operational standpoint to restart at this time. The plant's readiness for startup has been demonstrated during four previous hot functional tests; the latest of which was conducted in April of this year. There were no significant problems during this test, and the plant personnel

-successfully demonstrated their ability to operate the plant safely and efficiently.

'IMI-1 will ccmmence final heatup and proceed into the startup sequence after the Conmission lifts the innediate effectiveness of its July and August 1979 shutdown orders. The startup test program involves heating up the plant to hot shutdown conditions using non-nuclear heat and conducting prescribed tests and training at designated power levels, up to and including full power. Specific hold points have been-established in the power escalation program for senior management review of results and perfornance prior to granting approval to proceed.

In addition, it is my u:xlerstanding that, at various stages in the power.

ascension program, the NRC Staff will review our results and performance before authorizing escalation to higher power levels.

6. _ 'Ihe restart picf.am is scheduled to take approximately 99 days to conplete before the plant reaches sustained full power cperation..

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Attached hereto as exhibits are_ step.-by-step, detailed sequence documents which depict the controlled and methodical plan we intend to follow from plant heatup till full-power operation. Although we anticipate that the

' program will take 99 days, it is inportant to note that the sequence doctnents do not have a time scale. We will perform the steps in a controlled manner ensuring each one is performed satisfactorily prior to beginning the next step without concern for how long it takes. The sequence h w nts relating to heatup identify the steps followed during the last plant heatup in April of this year; the prwcuu to be followed after. restart authorization will be similar. The remaining sequence documents, covering the power escalation and testing program, depict the currently anticipated program; minor changes are likely. These sequence documents illustrate a nuttber of inportant points about the startup process:

(a) that the process consists of numerous steps, each of which must be coupleted before beginning the next step, (b) that the process is highly. structured and controlled permitting power escalation only after all necessary prerequisites are cmpleted successfully, (c) that @ U

-Nuclear has planned and scheduled the process _in a careful and deliberate manner to best protect the public health and safety, and (d) that appropriate consideration has been given to both GPU Nuclear and NEC review and anatlysis of test results and personnel performance to fcrther ensure the public health and safety.

7.

The basic sequence and scheduled time durations for the test c

prograa are as follows:

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(a). Final Heatu? and Surveillance Testing:

5 days required-to heatup tw plant using non-nuclear. heat to hot shutdown conditions.

In. addition, surveillances (required-tests and inspection of equipment and systems) necessary prior to: criticality.will be conducted during this period.

(b)

Zero and Iow Power Physics Testing:. Initial criticality,.

followed by 2 days of zero and low power! physics testing

~to verify and measure parameters associated with the refueled oore, such as teroperature coefficients, rod worth measurements, and shutdown margin verification.

(c) 3% Power Testing:

3 days of testing for_ verification and training of operators in natural and forced primary coolant circulation. Emergency feedwater autcznatic initiation and steam generator water level controls will also be tested during.this' period.

. (d) 15% Power Testing:

2 days of testing consisting of nuclear and thermal power calibrations, integrated control system.

~("ICS") tuning, and ccxamerx:ement of turbine generator

' initial. testing and operation.

(e) 25% Power Testinc':

2 days of testing to continue turbine operation, inclucing overspeed trip testing and further-ICS tuning.

(f) 40% Power Testing:

5 days for core power distribution measurements, including incore detector testing and power inblance detector correlation. At the end of this power

. plateau, a verification of plant performance will be conducted by initiating a loss of main feedwater resulting in a turbine and reactor trip.

(g) 48% Power: A month for required operator training and plant performance monitoring, as specified in the license.

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- (h) 75% Power Testing:

5 days for~ core power distribution measurements, including incore detector testing. Additionally, turbine gene.rator and ICS performance will be monitored and adjusted during this period.

(i) 75% Power: A:Tonth for required operator training and plant perforrance monitoring, as specified in the license.

(j) 100% Power Testing: 5 days of testing, including final verification of core physics parameters and final ICS tuning.

-This testing will be concluded by verification of plant

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' response to a turbine / reactor trip at 100% power.'

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(k): Recovery to 100% Operation: 10. days set aside for

~ corrective maintenance.as-required, management review

'of plant and operator performance during-the: test program, and recovery of the plant to full-power operation.

8.

This schedule: reflects our best current estimate of the time necessary =to allow us to safely, carefully, ard in a-controlled manner i'

emplete the' restart test program. ' The. test prcymu has been approved-

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by the' NRC Staff and must be conducted.in the sequence ' described.

!No progress beyond final heatup and surveillance testing can be acomplished

without a Caumission ordes authorizing restart. Any delay-in obtaining u

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restart; authorization will. result'in.a day--for-day.. delay in' achieving full-power operation.-

9. _ One of 'the prinary purposes of the restart test progmu is to-

' verify: satisfactory performance of. equipment, systems and personnel which I~

cannot be confirmed during hot shutdown testing. Correction of any problem encountered takes additional time and cannot be'acccuplished'~until 4

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' after. the~ test program is allowed to begin. Thus, irrespective of any

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delays encountered-during the program, a delay in obtaining permission to' restart will result in an equivalent Malay in ccupletion of the restart

. test program and return to full-power operation.

- 10. - l The 'IMI-l operating staff is manned, equipped,' and trained to safely and efficiently restart the plant, conduct the restart-test program,

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Fand return the plant to normal full-power operation.. The' controlled, sequence nature of the test program, with its gradual escalation of power, i

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'further minimizes. the risk to the public health and safety. Because'TMI-l

-has been shutdown for an extended period of time,.the inventory of radioactive fission products that might be released in the event.of-an s

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i accident is' less than that of a reactor operating at full-power and j

steady-sta'te conditions. Thus, the risk to the public from release of such materials at 'IMI-l during the test ptwtam is substantially less than for a plant operating at full power.

In addition, because TMI-l has been shutdown for mre than six years, the amount of decay heat

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which mst be renoved by emergency systems during any unanticipated event also is less than for reactors operating at full power for long periods of tirre. This reduction in decay heat places less stress on the emergency equignent, provides plant operators with a longer period of time to respond, and generally provides a greater margin of safety. All of these factors further minimize the risk to the public from the TMI-l restart test program.

h.

'H D. Hukfll, Jr. y Sworn to and subscribed before me this g day of May, 1985

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